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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.5
- 수록면
- 1,781 - 1,788 (8page)
- DOI
- https://doi.org/10.1016/j.net.2021.11.015
이용수
초록· 키워드
오류제보하기
The containment building Kori Unit 1 may require sequential steps for full decommissioning. This studyassumes that the containment building is to be used as an auxiliary building that handles nuclear powersystems and materials during decommissioning before conversion into a greenfield. Through the derivation of guidelines and dose evaluation, it was confirmed whether the radiation workers were satisfiedwith the ALARA decision. The specific modeling of the external radiation exposure was performed basedon the facility investigation procedures. The external radiation specific derived concentration guidelinelevels (DCGLs) for radiation workers in containment building were obtained using the RESRAD-BUILDcode and were applied to the VISIPLAN 3D ALARA Planning Tool code to calculate the working doseand check worker safety. The derivation of site-specific and realistic DCGLs and dose evaluation via 3Dmodeling can contribute to the scenario development for the decommission and remediation ofcontainment building
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